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Denman.Rmd
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---
name: Matthew
surname: Denman
position: "Nuclear Power Probabilistic Risk Analyst"
address: "Kairos Power"
phone: +1(617)999-2848
email: "denman@kairospower.com"
github: mrdenman-nuclear
linkedin: matthew-denman-86ab3615
date: "`r format(Sys.time(), '%B %Y')`"
output: vitae::moderncv
---
```{r setup, include=FALSE}
knitr::opts_chunk$set(echo = FALSE, warning = FALSE, message = FALSE)
library(vitae)
library(tidyverse)
```
# Education
```{r}
tribble(
~ Degree, ~ Year, ~ Institution, ~ Where,
"Doctor of Philosophy in Nuclear Engineering", "2007-2011", "Massachusetts Institute of Technology", "Cambridge MA",
"Bachelor of Science in Nuclear Engineering", "2003-2007", "University of Florida", "Gainesville, FL"
) %>%
detailed_entries(Degree, Year, Institution, Where)
```
# Work History
```{r}
tribble(
~ Employeer, ~ Year, ~ Position, ~ Where,
"Kairos Power", "2019-Present", "Principal Engineer, Reliability Engineering", "Albuquerque, NM"
) %>%
detailed_entries(Employeer, Year, Position, Where)
```
* Responsible Engineer, architect, and lead modeler for the Hermes reactor's
Maximum Hypothetical Accident (MHA). The Hermes MHA is the first MHA developed
for specifically for a reactor with a "functional containment" safety case.
The Hermes MHA is found in Chapter 13 of the Hermes Construction Permit
Application.
* Responsible Engineer for the Hermes reactor's Steady State Effluent Release
and associated off-site dose methodology development and analysis.
The Hermes MHA is found in Chapter 13 of the Hermes Construction Permit
Application.
* Responsible Engineer for the Kairos Power Fluoride Salt-Cooled High
Temperature Reactor (KP-FHR) Mechanistic Source Term methodology development
project which resulted in the first Nuclear Regulatory Commission approved
topical report. The first revision of the submitted in June, 2020 and the
Safety Evaluation was issued in April 2022.
* Contributor to the development of the KP-FHR Risk-Informed Performance-Based Licensing Basis Development Methodology Topical Report focusing on LBE and SSC classification.
\vspace{10pt}
```{r}
tribble(
~ Employeer, ~ Year, ~ Position, ~ Where,
"Sandia National Laboratories, Nuclear Energy Systems", "2017-2019", "Principal Member of the Techncial Staff", "Albuquerque, NM"
) %>%
detailed_entries(Employeer, Year, Position, Where)
```
* Principal Investigator for the reconstitution of the Centralized Reliability Database Organization (CREDO) database to support Probabilistic Risk Assessments and Safety Analysis for Sodium Fast Reactors.
* Project Manager for joint Japanese Atomic Energy Agency and Sandia bilateral (through the Civil Nuclear Energy Working Group) research effort to benchmark effort for sodium fire codes using Sandia Lab Directed Research and Development funded sodium fire test data.
* Project Manager for the incorporation of sodium fire models into the MELCOR computer code.
* Principal Investigator for an Office of New Reactors evaluation of scoping source terms for High Temperature Gas Reactors, Liquid Fueled Molten Salt Reactors, and Sodium Fast Reactors and developing Risk-Informed Security Criteria.
* Contributing Investigator responsible for the Level 2 Spent Fuel Pool PRA development as part of the NRC Level 3 PRA project.
* Participant in the development of the Generation 4 International Forum Sodium Fast Reactor Safety Design Guidelines Task Force.
\vspace{10pt}
```{r}
tribble(
~ Employeer, ~ Year, ~ Position, ~ Where,
"Sandia National Laboratories, Nuclear Energy Systems", "2011-2017", "Senior Member of the Techncial Staff", "Albuquerque, NM"
) %>%
detailed_entries(Employeer, Year, Position, Where)
```
* Contributing Investigator responsible for the development of uncertainty distributions for Safety Relief Valve failure, Safety Vent Valve failure, Decay Heat, and Core Collapse parameters in the Surry and Sequoyah SOARCA Uncertainty Analysis.
* Investigator responsible for characterizing of uncertainties and sensitivity studies on the Fukushima 1F1 accident analysis using MELCOR.
* Principal Investigator for a multi-institute, multi-disciplinary examination of safety and licensing gaps for the Sodium Fast Reactor.
* Principal Investigator of a Lab Directed Research and Development project to create the mathematical formulation for Dynamic Fault Trees to inform decision makers of evolving state of support system success probability mid-accident.
* Principal investigator for a two proof-of-concept Level 2 Risk Assessments to inform the development of Severe Accident Management Guidelines for both integral Pressurized Water Reactors and Sodium Fast Reactors, using a combination of:
* Severe accident simulation (via MELCOR and SAS4a codes),
* Discrete Dynamic Event Trees via the ADAPT code, and
* Decision analysis using Bayesian Networks.
\vspace{10pt}
```{r}
tribble(
~ Employeer, ~ Year, ~ Position, ~ Where,
"Sandia National Laboratories, Annular Core Research Reactor", "2007", "Nuclear Engineering Intern", "Albuquerque, NM"
) %>%
detailed_entries(Employeer, Year, Position, Where)
```
Created relativity pulse magnitude predictive models to account for the effects of spectrum filter buckets using data derived through experimentation and MCNP simulation.
\vspace{10pt}
```{r}
library(tibble)
tribble(
~ Employeer, ~ Year, ~ Position, ~ Where,
"Florida Power and Light, Mechanical and Component Engineering", "2006", "Mechanical Engineering Intern", "Port St. Lucie, FL"
) %>%
detailed_entries(Employeer, Year, Position, Where)
```
Conducted preventive maintenance on auxiliary feed-water pumps, diesel air-start motors, and radioactive waste management systems. Assisted with low power physics testing and approach to critical procedures coming out of the PSL 2-16 outage.
\vspace{10pt}
```{r}
tribble(
~ Employeer, ~ Year, ~ Position, ~ Where,
"Florida Power and Light, Nuclear Fuels Division", "2005", "Nuclear Engineering Intern", "Juno Beach, FL"
) %>%
detailed_entries(Employeer, Year, Position, Where)
```
Modeled potential particle blockage in spacer grids for pressurized water reactor fuel assemblies to address GSI-191 concerns for the Port St. Lucie 1&2, Turkey Point 3&4, and Seabrook nuclear reactors.
# Professional Society Postions
## Joint Committee of Nuclear Risk Management
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Sub-Committee of Standards Development", "2019-Present", "Chair", "Facilitating New Standards"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Sub-Committee of Standards Development", "2017-2018", "Vice-Chair", "Facilitate Chair"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Main Committee", "2018-Present", "Member", "Comment and Vote on Standards"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
## Nuclear Installation Safety Division
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Executive Committee", "2018-2019", "Chair", "Budget and Plan Activities"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Executive Committee", "2017-2018", "Vice-Chair", "Cross-Division Representation"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Program Committee", "2014-2015", "Chair", "Organized NISD Sessions for ANS"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Program Committee", "2013-2014", "Vice-Chair", "Division Representative to ANS"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Program Committee", "2012-2013", "Secretary", "Record Keeping"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
## ANS Trinity
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Executive Committee", "2019-2020", "Chair", "Organize and Run Dinner Meetings"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
```{r}
tribble(
~ Group, ~ Year, ~ Position, ~ Responsibility,
"Executive Committee", "2018-2019", "Vice-Char", "Faciliate Chair"
) %>%
detailed_entries(Group, Year, Position, Responsibility)
```
# Programming Experience
```{r, echo=FALSE}
library(gt)
tribble(
~lang, ~apps,
"GitHub", "Code Review, Issues Tracking, Work Planning",
"R", "Generating Documents and Websites; Data Cleaning",
"LaTeX", "Reports, Memos, and Journals",
"Python", "Input Generation; Automation; Post-prossessing",
"Matlab", "Input Generation; Automation; Post-prossessing; Statistics",
"Fortran", "School Assignments"
) %>%
gt() %>%
tab_options(
table.width = pct(100)
) %>%
tab_header(
title = md("My Programming Journey"),
subtitle = md("Most Recent Experience is Listed First")
) %>%
tab_row_group(
group = "Basic Coding",
rows = 4:6
) %>%
tab_row_group(
group = "Analysis as Code",
rows = 2:3
) %>%
tab_row_group(
group = "Version Control",
rows = 1:1
) %>%
cols_label(
lang = md("Language"),
apps = md("Applications")
)
```
# Awards and Certificates
* 2021 - ANS NISD: David Okrent Award for Nuclear Safety
* 2020 - JCNRM Certificate of Acclimation for technical contributions to the ANLWR PRA Standard
* 2019 - ANS Certificate of Governance, Chair, NISD, 2018-2019
* 2011 - MIT College of Engineering Reinhold Rudenberg Memorial Prize
* 2009 - ANS Student Conference Best Fast Reactor Presentation
* 2007 - ANS Student Conference Best in Poster Competition
* Honor Societies:
* Alpha Nu Sigma
* Tau Beta Pi
* Professional Development Courses:
* 2012 - Decision-Making, Design, and Strategy Under Uncertainty
* 2014 - Tackling the Challenges of Big Data, MIT
* 2016 - Nuclear Plant Safety, MIT (Most Persistent Questioner Award)
# Publications
## Techncial Reports
```{r}
vitae::bibliography_entries('reports.bib')
```
## Journals
```{r}
vitae::bibliography_entries('journals.bib')
```
## Conferences
```{r}
vitae::bibliography_entries('conferences.bib')
```
## Panels
```{r}
vitae::bibliography_entries('panels.bib')
```